Defect Distributions and Transport in Nanocomposites: A Theoretical Perspective
|
|
- Agnes Reeves
- 5 years ago
- Views:
Transcription
1 University of Nebraska - Lincoln DigitalCommons@University of Nebraska - Lincoln NCESR Publications and Research Energy Sciences Research, Nebraska Center for Defect Distributions and Transport in Nanocomposites: A Theoretical Perspective Blas Pedro Uberuaga Los Alamos National Laboratory, blas@lanl.gov Enrique Martinez Los Alamos National Laboratory Zhenxing Bi Los Alamos National Laboratory Mujin Zhuo Los Alamos National Laboratory, Michael Nastasi University of Nebraska-Lincoln, mnastasi@unl.edu See next page for additional authors Follow this and additional works at: Uberuaga, Blas Pedro; Martinez, Enrique; Bi, Zhenxing; Zhuo, Mujin; Nastasi, Michael; Misra, Amit; and Caro, Alfredo, "Defect Distributions and Transport in Nanocomposites: A Theoretical Perspective" (). NCESR Publications and Research.. This Article is brought to you for free and open access by the Energy Sciences Research, Nebraska Center for at DigitalCommons@University of Nebraska - Lincoln. It has been accepted for inclusion in NCESR Publications and Research by an authorized administrator of DigitalCommons@University of Nebraska - Lincoln.
2 Authors Blas Pedro Uberuaga, Enrique Martinez, Zhenxing Bi, Mujin Zhuo, Michael Nastasi, Amit Misra, and Alfredo Caro This article is available at of Nebraska - Lincoln:
3 Mater. Res. Lett., Defect Distributions and Transport in Nanocomposites: A Theoretical Perspective Blas Pedro Uberuaga a,, Enrique Martinez a, Zhenxing Bi b, Mujin Zhuo b, Quanxi Jia b, Michael Nastasi c, Amit Misra b and Alfredo Caro a a Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM, USA; b Materials Physics and Applications Division, Los Alamos National Laboratory, Los Alamos, NM, USA; c Nebraska Center for Energy Sciences Research, University of Nebraska-Lincoln, Lincoln, NE, USA (Received April ; final version received May ) Nanomaterials are attracting great interest for many applications, including radiation tolerance. Most work on radiation effects in nanomaterials has focused on the interfaces. Here, we examine the other aspect of nanocomposites, the dual phase nature. Solving a reaction diffusion model of irradiated composites, we identify three regimes of steady-state behavior that depend on the defect properties in the two phases. We conclude that defect evolution in one phase depends on the defect properties in the other phase, offering a route to controlling defect evolution in these materials. These results have broad implications for nanomaterials more generally. Keywords: Nanocomposites, Radiation Effects, Defect Evolution Nanomaterials are increasingly finding application in a wide range of technologies, from solar energy conversation [] to fast ion conduction [] to magnetic materials.[] For many of these applications, the critical factor that favors nanomaterials over larger grained alternatives is the behavior of defects within the material, either because of enhanced mass transport or increased reactivity of defects. These factors are particularly important for developing radiation-tolerant materials, where enhanced defect recombination and annihilation result in overall improved resistance to radiationinduced damage mechanisms, such as swelling [] and embrittlement.[] Much attention has been devoted to the role that the interfaces in nanocomposites play on the radiation tolerance of nanocomposites.[6,7] It has been long understood that these interfaces can act as sinks for radiation-induced defects and mitigate their accumulation.[8 ] More recent work has connected the propensity for interfaces to interact with defects and gases with the atomic structure of those interfaces, offering new possibilities for engineering the radiation tolerance of materials by designing materials with specific types of interfaces.[] Given that nanomaterials maximize the density of such interfaces, the field of radiation damage in nanomaterials has seen considerable growth in recent years.[ 6] One aspect that has been overlooked is the role that the composite phases themselves have on the defect evolution in the material. To date, most attention has been focused on the role of the interfaces [7] and not the component phases. In series of recent papers,[8 ] (Z. Bi, private communication) the radiation damage behavior in a special class of oxide heterointerfaces, interfaces that are nearly perfectly coherent, were examined both experimentally and theoretically. It was found that, under similar radiation conditions, the response of a given material on one side of the interface was very sensitive to the composition of the material on the other side of the interface, as illustrated in Figure. In particular, the behavior of SrTiO (STO) in these three experiments is very different. In one case (TiO /SrTiO ), a thin amorphous layer forms on the STO side. In the case of BaTiO /STO, no amorphization is observed. Finally, in the case of STO/LaAlO, the STO side amorphizes to a great extent. In the TiO /STO sample, the formation of a defect denuded zone at the interface on the TiO side was also observed. This wide variety in behavior occurs even though atomistic modeling revealed that there were Corresponding author. blas@buber.net, blas@lanl.gov Blas Pedro Uberuaga, Enrique Martinez, Zhenxing Bi, Mujin Zhuo, Quanxi Jia, Michael Nastasi, Amit Misra and Alfredo Caro. Published by Taylor & Francis. This is an Open Access article distributed under the terms of the Creative Commons Attribution License ( which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. The moral rights of the named author(s) have been asserted.
4 Mater. Res. Lett., (a) (b) (c) (d) Figure. Examples of the irradiation response of different oxide heterointerfaces: (a) TiO /SrTiO, (b) BaTiO /SrTiO, and (c) SrTiO /LaAlO. In each case, the film thickness was between and nm and the irradiation conditions were chosen such that about dpa occurred just under the interface. In each case, the energy of the implanted Ne and the total fluence were (top) kev,. 6 ions/cm, (middle) kev,. 6 ions/cm, and (bottom) 6 kev, 8. ions/cm. The positions of the denuded zone and amorphous layers are labeled. The scale bar for all three images is the same. (d) Schematic of the typical energetic landscape for point defects as determined from atomistic calculations. Details about these experiments and the corresponding atomistic calculations can be found in [8,] (Z. Bi, private communication). no thermodynamic trap states for defects at these interfaces. Rather, it was hypothesized that the controlling parameters were the defect properties within each of the bulk phases and that the interface simply acted as a transition point between the two materials. In particular, it was argued that the formation and migration energies of defects within each phase determined the eventual behavior at the interface. The formation energies dictated the direction of flow of defects, while the migration energies dictated the rate of defect flow. Here, we solve a reaction diffusion model of point defect evolution in the presence of an interface between two materials in an arbitrary composite. We demonstrate that the behavior of defects at the interface can be quite complex, with multiple steady-state regimes possible. Transient behavior leading to steady-state conditions can be even more complex. We conclude that the defect evolution and distributions within a nanocomposite are very sensitive to the properties of the component phases. This has important consequences for not only radiation tolerance, but also other applications where defect behavior is critical. The parameters of the model consist of the defect properties within each material: the formation energy (or chemical potential at T = K, μ ) and the migration energy E m, both of which depend on which phase the defect resides in. Two types of defects are considered, nominally an and a. The simulation is spatially discretized into cells in which the local defect is tracked. The defect population within a cell j at time t can change with time via an explicit finite difference discretization scheme for the diffusion equation (shown for s I, but an equivalent equation exists for vacancies V ): c j I (t) =cj I (t δt) + S I K VI c j I (t δt)cj V (t δt) + c j+ I (t δt)k j+ j I + c j I (t δt)k j j I c j I (t δt)kj j+ I c j I (t δt)kj j I, () where c j I is the of s in cell j, S I is the production rate of s, K VI is the rate coefficient for annihilation, and k are rates for defects to move from one cell to a neighboring cell. k = ν exp( E m /k B T), where k B is the Boltzmann constant, T is temperature, ν is a rate prefactor, and E m are the migration energies. In each cell, the migration energy for the given defect is determined by its value in the given phase; for cells just on either side of the interface, the migration energies are modified by the difference in chemical potential μ for the defect. The basic landscape of the model is schematically illustrated in Figure (d). Note that this model does not contain any special behavior at the interface beyond a simple transition point between one material with one set of defect properties to another. Distances and times are given in arbitrary units as a choice of length scale sets the time scale via the ratio dt/dx. Thus, changing the relevant length scale simply scales the time scale but the resulting curve is unchanged. For the simulations reported in Figs., K IV was. cm /s, S (both species) was./cm /s, v was. cm /s, and T =, K. For the simulations reported in Fig. 6, K IV was. cm /s, S (both species) was./cm /s, v was. cm /s, and T = K. We first examine the behavior predicted by the model as a function of the parameters that describe the basic material properties. The values of the parameters for all of the figures are given in Table. We identify three regimes of steady-state behavior that describe different evolution of the defects at the interface. These regimes are illustrated in Figure. In the first regime, the s of both defects are enhanced on one side of the interface and depleted on the other, relative to the steadystate in the center of the layer. In the second regime, both defects achieve a flat profile in each layer, but in one layer s have a higher than vacancies, and the opposite is true in the other layer. The third regime is in some sense an intermediate case in which there is slight enhancement and
5 Mater. Res. Lett., Table. Model parameters used to generate the results in the various figures. Figure Parameter (a) (b) (c) (a) (b) EV ma C.. EI ma... C.. EV mb... C.. EI mb... C.. μ V C μ I C Notes: μ are defined relative to phase B: μ = μ A μ B. C indicates that the variable was varied in the plot and that all parameters had the same value. Negative values of chemical potential indicate that the defect prefers to reside in phase A. depletion of one defect at the interface, while the other defect sees no discontinuous spike at the interface. It is interesting to note that there is no regime in which the is enhanced at the interface on one side and the on the other side. In the first regime, the chemical potential differences of both defects are the same, such that both defects have a thermodynamic tendency to flow from phase A to phase B. Because the annihilation rate is smaller, in these simulations, than the diffusion rate, as defects flow from A to B, there is a depletion of both defects in the interfacial region of phase A and an accumulation in phase B, which persists independent of the rate of flow of defects within the material. That is, even if the defects flow quickly in both materials, the spikes still exist. The differences in the behavior of the two defects in the different regions of the material are dictated by the different kinetic properties of each. Interestingly, even though both defects have the same thermodynamic driving force to move from phase A to phase B, because of the differences in kinetics, the defect populations are inverted in each phase. In regime, the chemical potential is equal but opposite for both defects and the thermodynamic tendency for flow is also opposite. In this case, annihilation is small because there is never any appreciable of one or the other defect in a given phase of the composite. Finally, regime represents an intermediate case. Here, one of the defects is depleted on one side of the interface and enriched on the other, but the second defect only exhibits depletion and, unlike in the other cases, is continuous across the interface. While the generic behavior is reminiscent of regime, rather than being driven by the differences in thermodynamic (a) (arbitrary units).. I V (b). (arbitrary units).. I V (c). (arbitrary units).. I V Figure. Three regimes of defect behavior at the composite interface discussed in the text: (a) regime, (b) regime, and (c) regime. The shaded region represents one phase, while the white region is the other phase. Interstitial s are indicated by the solid lines, while s are indicated by the points. (a) (arbitrary units) (b) (arbitrary units) Figure. (a) Steady-state s for s as a function of migration barriers, depicted in the legend and having units of ev. The parameters are chosen such that the s are identical. (b) Steady-state s for s as a function of chemical potential, depicted in the legend and having units of ev.
6 Mater. Res. Lett., properties of the defects in the two phases, the profiles are driven by the kinetics: both defects have the same thermodynamic driving force to flow from phase A to phase B, but the s are inverted with respect to one another. Figure (a), in addition to demonstrating nonuniform defect s at the interface, also reveals that the defect s in the center of each layer is very sensitive to the defect kinetics. In this particular case, the chemical potentials of each defect are identical, the only differences are in the migration energies. This suggests that the steady-state of defects in one phase of the composite can be controlled to a high degree by the kinetic properties in the other phase. This is demonstrated more explicitly in Figure, which shows the steady-state s of s for a series of cases in which the chemical potential differences for both defects are equal and held constant and all of the migration energies are equal but varied (EI ma = EI mb = EV ma = EV mb ). By varying the migration energies by.6 ev, the behavior at the interface and the average in each phase changes significantly, with more defects flowing from phase A to phase B as the kinetics are increased. Similarly, in cases when the thermodynamic driving forces for flow of the two defects is in opposite directions ( μ V = μ I ), there is a strong dependence of the defect content in one material on the relative defect formation energies in the other material, as would be expected. This is illustrated in Figure (b) in which the kinetic properties of all defects are held constant while the differences in chemical potentials are varied. In this case, in which the defect thermodynamics dominate over the kinetics, very large changes in defect content are possible. Again, this points to the fact that the defect population in one phase can be influenced by the properties of the neighboring phase. All of the above discussion refers to results of the model once it has reached a steady-state condition. In many materials examined in laboratory conditions where temperatures might be moderate, the material does not often reach steady state. This is particularly true of oxide ceramics in which migration energies are often quite high and many defects produced under irradiation have very little mobility. To better understand how the transient behavior might differ from the steadystate behavior, in Figure we examine a case in which the steady-state behavior is characteristic of regime, but the transient behavior exhibits much more complex defect behavior. As a function of time, defect s at the interface become significantly enhanced and depleted. In particular, the defect enhancement at the interface is higher than the eventually steady-state s. Thus, in this particular case, even if the material is able to accommodate the steady-state defect s, transient spikes might lead to situations (arbitrary units) Figure. Defect s as a function of time. The values of time, in arbitrary units, are given in the legend and represent an order of magnitude increase in simulation time for each curve. in which the material fails due to unsustainable levels of defects. Finally, to better understand how the properties of defects in one phase influence the behavior in the other phase, we consider another set of simulations meant to mimic a composite in which one phase is Cu and the other phase is an arbitrary material. Thus, in the Cu phase, we set EV m =.7 ev and Em I = ev. The properties of the defects in phase A are then systematically varied. The resulting s of s and vacancies at the interface in the Cu phase at steady state are reported in Figure. As can be seen from the figure, the defect s in the Cu phase vary significantly with the properties of phase A, with s varying for a given set of chemical potentials by as much as times and s by as much as times. Further, as the relative chemical potential of defects are varied, peak s of defects vary by about two orders of magnitude. Thus, there is a very strong coupling between the defect response in the Cu phase with the defect properties in phase A. These results lead to the conclusion that defect evolution in composites is critically dependent on the composition of the composite. Further, the radiation damage response of the composite cannot be viewed as the isolated response of each component material. It is precisely through their coupling, even independent of the properties of the interfaces that connect them, that their response is determined. This model is rather basic and neglects a number of features that would be present in real materials. First, we assume that defects of all types can exist in both phases of the composite. This might be reasonable for complex oxide composites such as TiO /SrTiO in which, for example, Ti s and vacancies can exist in both phases. It would also be reasonable for amorphous/crystalline composites or materials composed of, for example, Fe in both fcc and bcc phases.
7 Mater. Res. Lett., Chemical Potential A Cu A Cu A Cu A Cu Interstitial Vacancy Figure. Dependence on the and s on the Cu side of the interface as a function of the properties of phase A. The axes in each figure are the migration energies of s and vacancies in phase A, in ev. The schematic differences in chemical potential are listed at the top where the dashed (red) line indicates the relative chemical potential for s and the solid (blue) line is that for vacancies. However, more generally, a in one phase can only exist in the other by considering the enthalpy of mixing (consider, for example, a Nb in a Cu/Nb composite). In such a case, as the moves from one phase to the other, a backward flux of atoms of the second phase would cross the interface, leading to intermixing. We have also assumed a dilute limit in which the only defect defect interaction is annihilation. In real systems, defects can agglomerate, leading to extended defect clusters that have their own kinetic and thermodynamic properties. Finally, we have, in the end, only explored a relatively small region of the possible phase space of the model. We have not systematically examined the role of the defect production rate, internal sinks (such as dislocations), or the strength of the annihilation on the predicted results. Further, for reasons of numerical stability, we have only varied E m and μ within a relatively small window. The relevant migration energies and chemical potentials in many oxide composites are much larger. Thus, there could be other regimes present in the model. That said, once E m is large enough, for example, increasing it further will not influence the results as the defects have crossed a threshold of mobility. We therefore expect that the results presented here represent the range of behavior possible in the system. In spite of these simplifying assumptions, we expect that the basic insight provided by this simple model will have some applicability to composites more generally and provide new avenues for exploring the radiation tolerance of complex materials. The model reproduces the basic features seen in the experiments summarized in Figure, suggesting that, even in its simplicity, this model accounts for the basic processes that govern the behavior seen in these materials. In regime, there is a depletion of defects on one side of the interface (a denuded zone ) and an enhancement on the other side, which could lead to amorphization, as found in TiO /SrTiO (Figure (a)). If the chemical potentials are equal μ =, there is no flow of defects from one phase to the other and no special behavior at the interface, as in BaTiO /SrTiO. That said, there are certainly a number of other factors that influence radiation damage in nanomaterials, including the mechanisms for recombination,[] the energetics of the interfaces themselves,[7] and the role of trap states at the interfaces.[ ] A comprehensive model of radiation damage evolution in nanomaterials would need to account for all of these factors. The simple model presented here, however, suggests that the relative properties of point defects in the different phases of a nanocomposite are of great importance. It is useful to compare the behavior predicted by this model with literature results on irradiation studies of composites. Relatively few studies of irradiation effects in composites have analyzed the relative radiation tolerance of the two phases. One particularly interesting example involves ZrO. Bulk ZrO is very difficult to amorphize, withstanding doses of 68 dpa,[] while nanocrystalline ZrO resists amorphization up to doses of at least 8 dpa.[6] In contrast, ZrO nanoparticles embedded in a SiO matrix were observed to amorphize by doses as little as dpa.[7] This has been rationalized as a consequence of the high energy of the interfaces in the composite when compared with the nanocrystalline material.[7,7] However, the present model would suggest that there is likely a thermodynamic driving force for defects to flow from one phase to the other, possibly destabilizing the ZrO phase and leading to its quick amorphization. Such a driving force would not exist in the nanocrystalline material. Further, it has been proposed that the behavior of He in oxide dispersion strengthened steels is dictated by a similar energy
8 Mater. Res. Lett., landscape, albeit one that also involves a trap state at the interface.[8] Thus, He implantation experiments might provide another avenue for validating the premises of the model presented here. Certainly, these results have important consequences for the development of nanocomposites for radiation tolerance, as the defect distributions within the material can be controlled to a great degree simply by choosing the appropriate component phases. However, the impact of these results is much broader. Any application of nanocomposites in which defect transport or distributions are critical will be affected by the flow of defects between the component phases, as determined by the diffusivities of the defects, and the relative chemical potentials of the defects. Indeed, a similar model has been proposed for mechanical alloying in Cu Al composites.[9] In addition, defect content and distributions are clearly important for the performance of fast ion conductors. Thus, there is great promise in engineering nanocomposites for such applications by optimizing the choice of the component phases. To conclude, using a simple reaction diffusion model, we have shown that the defect evolution in composites is very complex, depending critically on the composition of the composite. By varying the properties of one phase within the composite, the defect evolution within the other phase can be modified to a very high degree. This is true even in simple composites in which the interface has no special interaction with defects and merely acts as a transition point between two materials. These results suggest that the radiation damage of a composite material can be tailored by choosing the appropriate component materials. In particular, the radiation tolerance of a phase that has relatively poor radiation tolerance in single-phase form might be significantly enhanced by the appropriate selection of a second phase. As an approach to controlling radiation damage in complex materials, changing the component materials may be much more straightforward than engineering specific types of interfaces and, thus, these results have significant potential in leading to new radiation-tolerant composites. Acknowledgements This work was supported as part of the Center for Materials at Irradiation and Mechanical Extremes, an Energy Frontier Research Center funded by the U.S. Department of Energy (DOE), Office of Science, Office of Basic Energy Sciences under Award Number 8LANL6. Los Alamos National Laboratory, an affirmative action equal opportunity employer, is operated by Los Alamos National Security, LLC, for the National Nuclear Security Administration of the U.S. DOE under contract DE-AC-6NA96. References [] Kamat PV. Meeting the clean energy demand: nanostructure architectures for solar energy conversion. J Phys Chem C. 7;(7):8 86. [] Tuller HL. Ionic conduction in nanocrystalline materials. Solid State Ion. ;( ): 7. [] Herzer G. Modern soft magnets: amorphous and nanocrystalline materials. Acta Mat. ;6():78 7. [] Garner FA. Irradiation performance of cladding and structural steels in liquid metal reactors, Vol. A of Materials Science and Technology: A Comprehensive Treatment. Weinheim: VCH Publishers; 99. Chapter 6, p. 9. [] Porter DL, Garner FA. Irradiation creep and embrittlement behavior in AlSi 6 stainless-steel at very high neutron fluences. J Nucl Mater. 988:9;. [6] Misra A, Demkowicz MJ, Zhang X, Hoagland RG. The radiation damage tolerance of ultra-high strength nanolayered composites. JOM. 7;9:6 6. [7] Odette GR, Alinger MJ, Wirth BD. Recent developments in irradiation-resistant steels. Annu Rev Mater Res. 8:8;7. [8] Siegel RW, Chang SM, Balluffi RW. Vacancy loss at grainboundaries in quenched polycrystalline gold. Acta Metall. 98:8();9 7. [9] Thorsen PA, Bilde-Sorensen JB, Singh BN. Bubble formation at grain boundaries in helium implanted copper. Scr Mater. :(6);7 6. [] Barnes RS, Redding GB, Cottrell AH. The observation of sources in metals. Philos Mag. 98:(); [] Demkowicz MJ, Hoagland RG, Hirth JP. Interface structure and radiation damage resistance in Cu Nb multilayer nanocomposites. Phys Rev Lett. 8:(); 6-. [] Yamada R, Zinkle SJ, Pells GP. Defect formation in ion-irradiated Al O and MgAl O effects of grainboundaries and fusion transmutation products. J Nucl Mater. 99:9;6 6. [] Chimi Y, Iwase A, Ishikawa N, Kobiyama M, Inami T, Okuda S. Accumulation and recovery of defects in ion-irradiated nanocrystalline gold. J Nucl Mater. :97(); 7. [] Swaminathan N, Kamenski PJ, Morgan D, Szlufarska I. Effects of grain size and grain boundaries on defect production in nanocrystalline C-SiC. Acta Mater. :8(8);8 8. [] Shen TD, Feng S, Tang M, Valdez JA, Wang YQ, Sickafus KE. Enhanced radiation tolerance in nanocrystalline MgGa O. Appl Phys Lett. 7:9(6);6. [6] Landau P, Guo Q, Harrat K, Greer JR. The effect of he implantation on the tensile properties and microstructures of Cu/Fe nano-bicrystals. Adv Funct Mater. :();8 88. [7] Shen TD. Radiation tolerance in a nanostructure: is smaller better? Nucl Instrum Methods Phys Res B. 8:66(6);9 9. [8] Zhuo MJ, Fu EG, Yan L, Wang YQ, Zhang YY, Dickerson RM, Uberuaga BP, Misra A, Nastasi M, Jia QX. Interface-enhanced defect absorption between epitaxial anatase TiO film and single crystal SrTiO. Scr. Mater. :6(9);87 8. [9] Zhuo MJ, Uberuaga BP, Yan L, Fu EG, Dickerson RM, Wang YQ, Misra A, Nastasi M, Jia QX. Radiation damage at the coherent anatase TiO /SrTiO interface under Ne ion irradiation. J Nucl Mater. :9( );77 8. [] Bi Z, Uberuaga BP, Vernon LJ, Fu E, Wang YQ, Li N, Wang H, Misra A, Jia QX. Radiation damage in heteroepitaxial BaTiO thin films on SrTiO under Ne ion irradiation. J Appl Phys. :();. [] Swaminathan N, Morgan D, Szlufarska, I. Role of recombination kinetics and grain size in radiation-induced amorphization. Phys Rev B. :86();. 6
9 Mater. Res. Lett., [] Demkowicz MJ, Misra A, Caro A. The role of interface structure in controlling high helium s. Curr Opin Solid State Mater Sci. :6(); 8. [] Kolluri K, Demkowicz MJ. Formation, migration, and clustering of delocalized vacancies and s at a solid-state semicoherent interface. Phys Rev B. :8();6. [] Tschopp MA, Solanki KN, Gao F, Sun X, Khaleel MA, Horstmeyer MF. Probing grain boundary sink strength at the nanoscale: energetics and length scales of and absorption by grain boundaries in alpha-fe. Phys Rev B. :8(6);68. [] Sickafus KE, Matzke H, Hartmann T, Yasuda K, Valdez JA, Chodak P, Nastasi M, Verall RA. Radiation damage effects in zirconia. J Nucl Mater. 999:7( ); [6] Rose M, Gorzawski G, Miehe G, Balogh AG. Phase stability of nanostructured materials under heavy ion irradiation. Nanostruct Mater. 99:6( 8);7 7. [7] Meldrum A, Boatner LA, Ewing RC. Nanocrystalline zirconia can be amorphized by ion irradiation. Phys Rev Lett. ;88():-. [8] Erhart PJ. A first-principles study of helium storage in oxides and at oxide iron interfaces. Appl Phys. :();. [9] Khina BB, Solpan I, Lovshenko GF. Modelling accelerated solid-state diffusion under the action of intensive plastic deformation. J Mater Sci. :9(6 7); 8. 7
Experience with Moving from Dpa to Changes in Materials Properties
Experience with Moving from Dpa to Changes in Materials Properties Meimei Li, Argonne National Laboratory N. V. Mokhov, Fermilab 46 th ICFA Advanced Beam Dynamics Workshop Sept. 27 Oct. 1, 2010 Morschach,
More informationSCIENCE CHINA Physics, Mechanics & Astronomy
SCIENCE CHINA Physics, Mechanics & Astronomy Article April 2012 Vol.55 No.4: 614 618 doi: 10.1007/s11433-012-4679-8 Stability and diffusion properties of self-interstitial atoms in tungsten: a first-principles
More informationMolecular Dynamics Simulations of Fusion Materials: Challenges and Opportunities (Recent Developments)
Molecular Dynamics Simulations of Fusion Materials: Challenges and Opportunities (Recent Developments) Fei Gao gaofeium@umich.edu Limitations of MD Time scales Length scales (PBC help a lot) Accuracy of
More informationThermodynamic aspects of
Thermodynamic aspects of nanomaterials Advanced nanomaterials H.HofmannHofmann EPFL-LTP 2011/2012 ÉCOLE POLYTECHNIQUE FÉDÉRALE DE LAUSANNE Thermodynamic properties p of nanosized materials 100000 120 Total
More informationMultiscale modelling of D trapping in W
CMS Multiscale modelling of D trapping in W Kalle Heinola, Tommy Ahlgren and Kai Nordlund Department of Physics and Helsinki Institute of Physics University of Helsinki, Finland Contents Background Plasma-wall
More informationDIFFUSION IN SOLIDS. IE-114 Materials Science and General Chemistry Lecture-5
DIFFUSION IN SOLIDS IE-114 Materials Science and General Chemistry Lecture-5 Diffusion The mechanism by which matter is transported through matter. It is related to internal atomic movement. Atomic movement;
More informationRadiation damage I. Steve Fitzgerald.
Radiation damage I Steve Fitzgerald http://defects.materials.ox.ac.uk/ Firstly an apology Radiation damage is a vast area of research I cannot hope to cover much in any detail I will try and introduce
More information, MgAl 2. and MgO irradiated with high energy heavy ions O 3
Surface defects in Al 2, MgAl 2 O 4 and MgO irradiated with high energy heavy ions V.A.Skuratov 1, S.J. Zinkle 2 A.E.Efimov 1, K.Havancsak 3 1 Flerov Laboratory of Nuclear Reactions, JINR, Dubna, Russia
More informationTime accelerated Atomic Kinetic Monte Carlo for radiation damage modelling
PERFORM 60 FP7 Project Time accelerated Atomic Kinetic Monte Carlo for radiation damage modelling C. Domain, C.S. Becquart, R. Ngayam-Happy EDF R&D Dpt Matériaux & Mécanique des Composants Les Renardieres,
More informationChapter 4. Surface defects created by kev Xe ion irradiation on Ge
81 Chapter 4 Surface defects created by kev Xe ion irradiation on Ge 4.1. Introduction As high energy ions penetrate into a solid, those ions can deposit kinetic energy in two processes: electronic excitation
More informationComparison of deuterium retention for ion-irradiated and neutronirradiated
13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications / 1st International Conference on Fusion Energy Materials Science Comparison of deuterium retention for ion-irradiated
More informationCherry-Pit Structures in Binary Immiscible Alloy Under Ion Irradiation
Cherry-Pit Structures in Binary Immiscible Alloy Under Ion Irradiation Shipeng Shu, Kenneth Tussey May 8, 2011 Abstract We study an special microstructure (matrix atom riched small clusters inside the
More informationMolecular dynamics simulations of the clustering and dislocation loop punching behaviors of noble gas atoms in tungsten
Molecular dynamics simulations of the clustering and dislocation loop punching behaviors of noble gas atoms in tungsten J.Z.Fang, F.Zhou, H.Q.Deng, X.L.Gan, S.F.Xiao, W.Y.Hu Hunan University Contents I,
More informationRadiation Damage Effects in Solids. Los Alamos National Laboratory. Materials Science & Technology Division
Radiation Damage Effects in Solids Kurt Sickafus Los Alamos National Laboratory Materials Science & Technology Division Los Alamos, NM Acknowledgements: Yuri Osetsky, Stuart Maloy, Roger Smith, Scott Lillard,
More informationBi-directional phase transition of Cu/6H SiC( ) system discovered by positron beam study
Applied Surface Science 194 (2002) 278 282 Bi-directional phase transition of Cu/6H SiC(0 0 0 1) system discovered by positron beam study J.D. Zhang a,*, H.M. Weng b, Y.Y. Shan a, H.M. Ching a, C.D. Beling
More informationJ. Boisse 1,2, A. De Backer 1,3, C. Domain 4,5, C.S. Becquart 1,4
MODELLING SELF TRAPPING AND TRAP MUTATION IN TUNGSTEN USING DFT AND MOLECULAR DYNAMICS WITH AN EMPIRICAL POTENTIAL BASED ON DFT J. Boisse 1,2, A. De Backer 1,3, C. Domain 4,5, C.S. Becquart 1,4 1 Unité
More informationL. Gámez a, B. Gámez a, M.J. Caturla b '*, D. Terentyev c, J.M. Perlado 3 ABSTRACT
Object Kinetic Monte Carlo calculations of irradiated Fe-Cr dilute alloys: The effect of the interaction radius between substitutional Cr and self-interstitial Fe L. Gámez a, B. Gámez a, M.J. Caturla b
More informationJoint ICTP-IAEA Workshop on Physics of Radiation Effect and its Simulation for Non-Metallic Condensed Matter.
2359-3 Joint ICTP-IAEA Workshop on Physics of Radiation Effect and its Simulation for Non-Metallic Condensed Matter 13-24 August 2012 Electrically active defects in semiconductors induced by radiation
More informationDefects and diffusion in metal oxides: Challenges for first-principles modelling
Defects and diffusion in metal oxides: Challenges for first-principles modelling Karsten Albe, FG Materialmodellierung, TU Darmstadt Johan Pohl, Peter Agoston, Paul Erhart, Manuel Diehm FUNDING: ICTP Workshop
More informationTheory and experiment of nanostructure self-organization in irradiated materials
Journal of Computer-Aided Materials Design, 8: 1 38, 2002. KLUWER/ESCOM 2002 Kluwer Academic Publishers. Printed in the Netherlands. Theory and experiment of nanostructure self-organization in irradiated
More informationThermoelectric materials. Presentation in MENA5010 by Simen Nut Hansen Eliassen
Thermoelectric materials Presentation in MENA5010 by Simen Nut Hansen Eliassen Outline Motivation Background Efficiency Thermoelectrics goes nano Summary https://flowcharts.llnl.gov/archive.html Waste
More informationNITROGEN CONTAINING ULTRA THIN SiO 2 FILMS ON Si OBTAINED BY ION IMPLANTATION
NITROGEN CONTAINING ULTRA THIN SiO 2 FILMS ON Si OBTAINED BY ION IMPLANTATION Sashka Petrova Alexandrova 1, Evgenia Petrova Valcheva 2, Rumen Georgiev Kobilarov 1 1 Department of Applied Physics, Technical
More informationIon irradiation induced damage and dynamic recovery in single crystal silicon carbide and strontium titanate
University of Tennessee, Knoxville Trace: Tennessee Research and Creative Exchange Doctoral Dissertations Graduate School 8-2015 Ion irradiation induced damage and dynamic recovery in single crystal silicon
More informationMIT Amorphous Materials
MIT 3.071 Amorphous Materials 10: Electrical and Transport Properties Juejun (JJ) Hu 1 After-class reading list Fundamentals of Inorganic Glasses Ch. 14, Ch. 16 Introduction to Glass Science and Technology
More informationAu-C Au-Au. g(r) r/a. Supplementary Figures
g(r) Supplementary Figures 60 50 40 30 20 10 0 Au-C Au-Au 2 4 r/a 6 8 Supplementary Figure 1 Radial bond distributions for Au-C and Au-Au bond. The zero density regime between the first two peaks in g
More informationSupplementary Figure 1 A schematic representation of the different reaction mechanisms
Supplementary Figure 1 A schematic representation of the different reaction mechanisms observed in electrode materials for lithium batteries. Black circles: voids in the crystal structure, blue circles:
More informationJoint ICTP-IAEA Workshop on Physics of Radiation Effect and its Simulation for Non-Metallic Condensed Matter.
2359-23 Joint ICTP-IAEA Workshop on Physics of Radiation Effect and its Simulation for Non-Metallic Condensed Matter 13-24 August 2012 Overview of non-metallic materials for fusion applications S. M. González
More informationTMT4320 Nanomaterials November 10 th, Thin films by physical/chemical methods (From chapter 24 and 25)
1 TMT4320 Nanomaterials November 10 th, 2015 Thin films by physical/chemical methods (From chapter 24 and 25) 2 Thin films by physical/chemical methods Vapor-phase growth (compared to liquid-phase growth)
More informationAtomistic Simulation of Nuclear Materials
BEAR Launch 2013 24 th June 2013 Atomistic Simulation of Nuclear Materials Dr Mark S D Read School of Chemistry Nuclear Education and Research Centre www.chem.bham.ac.uk Birmingham Centre for Nuclear Education
More informationPerformance of MAX phase Ti 3 SiC 2 under the irradiation of He/H :
Performance of MAX phase Ti 3 SiC 2 under the irradiation of He/H : Elaboration from DFT Yuexia Wang Institute of Modern Physics Fudan University Hefei-2016 Materials Issues Neutron flux (14MeV, 0.5-0.8
More informationChapter 6 ELECTRICAL CONDUCTIVITY ANALYSIS
Chapter 6 ELECTRICAL CONDUCTIVITY ANALYSIS CHAPTER-6 6.1 Introduction The suitability and potentiality of a material for device applications can be determined from the frequency and temperature response
More informationmicromachines ISSN X
Micromachines 2014, 5, 359-372; doi:10.3390/mi5020359 Article OPEN ACCESS micromachines ISSN 2072-666X www.mdpi.com/journal/micromachines Laser Micro Bending Process of Ti6Al4V Square Bar Gang Chen and
More informationOpportunities for Advanced Plasma and Materials Research in National Security
Opportunities for Advanced Plasma and Materials Research in National Security Prof. J.P. Allain allain@purdue.edu School of Nuclear Engineering Purdue University Outline: Plasma and Materials Research
More informationAccelerated Neutral Atom Beam (ANAB)
Accelerated Neutral Atom Beam (ANAB) Development and Commercialization July 2015 1 Technological Progression Sometimes it is necessary to develop a completely new tool or enabling technology to meet future
More information31704 Dynamic Monte Carlo modeling of hydrogen isotope. reactive-diffusive transport in porous graphite
31704 Dynamic Monte Carlo modeling of hydrogen isotope reactive-diffusive transport in porous graphite * R. Schneider a, A. Rai a, A. Mutzke a, M. Warrier b,e. Salonen c, K. Nordlund d a Max-Planck-Institut
More informationCOMPUTATIONAL INVESTIGATION OF THE EFFECT OF CLUSTER IMPACT ENERGY ON THE MICROSTRUCTURE OF FILMS GROWN BY CLUSTER DEPOSITION
COMPUTATIONAL INVESTIGATION OF THE EFFECT OF CLUSTER IMPACT ENERGY ON THE MICROSTRUCTURE OF FILMS GROWN BY CLUSTER DEPOSITION AVINASH M. DONGARE, DEREK D. HASS, AND LEONID V. ZHIGILEI Department of Materials
More informationLecture 1: Atomic Diffusion
Part IB Materials Science & Metallurgy H. K. D. H. Bhadeshia Course A, Metals and Alloys Lecture 1: Atomic Diffusion Mass transport in a gas or liquid generally involves the flow of fluid (e.g. convection
More informationRadiation Effects in Solids
Radiation Effects in Solids NATO Science Series A Series presenting the results of scientific meetings supported under the NATO Science Programme. The Series is published by IOS Press, Amsterdam, and Springer
More informationINTRODUCTION TO THE DEFECT STATE IN MATERIALS
INTRODUCTION TO THE DEFECT STATE IN MATERIALS DEFECTS, DEFECTS, DEFECTS CAN T LIVE WITH THEM!!! CAN T LIVE WITHOUT THEM!!! INTRODUCTION TO DEFECT STATE IN MATERIALS DEFECTS, DEFECTS, DEFECTS Perfect crystals
More informationWhat so special about LaAlO3/SrTiO3 interface? Magnetism, Superconductivity and their coexistence at the interface
What so special about LaAlO3/SrTiO3 interface? Magnetism, Superconductivity and their coexistence at the interface Pramod Verma Indian Institute of Science, Bangalore 560012 July 24, 2014 Pramod Verma
More informationDFT modeling of novel materials for hydrogen storage
DFT modeling of novel materials for hydrogen storage Tejs Vegge 1, J Voss 1,2, Q Shi 1, HS Jacobsen 1, JS Hummelshøj 1,2, AS Pedersen 1, JK Nørskov 2 1 Materials Research Department, Risø National Laboratory,
More informationSize-dependent Metal-insulator Transition Random Materials Crystalline & Amorphous Purely Electronic Switching
Nanometallic RRAM I-Wei Chen Department of Materials Science and Engineering University of Pennsylvania Philadelphia, PA 19104 Nature Nano, 6, 237 (2011) Adv Mater,, 23, 3847 (2011) Adv Func Mater,, 22,
More informationNumerical Simulation of Radiation-Induced Chemical Segregation and Phase Transformation in a Binary System
Copyright 2013 Tech Science Press CMC, vol.38, no.2, pp.91-103, 2013 Numerical Simulation of Radiation-Induced Chemical Segregation and Phase Transformation in a Binary System Efraín Hernández-Rivera 1,2,
More informationNUCLEI, RADIOACTIVITY AND NUCLEAR REACTIONS
NUCLEI, RADIOACTIVITY AND NUCLEAR REACTIONS VERY SHORT ANSWER QUESTIONS Q-1. Which of the two is bigger 1 kwh or 1 MeV? Q-2. What should be the approximate minimum energy of a gamma ray photon for pair
More informationHelium bubbles in bcc Fe and their interactions with irradiation
Loughborough University Institutional Repository Helium bubbles in bcc Fe and their interactions with irradiation This item was submitted to Loughborough University's Institutional Repository by the/an
More informationThermodynamic calculations on the catalytic growth of carbon nanotubes
Thermodynamic calculations on the catalytic growth of carbon nanotubes Christian Klinke, Jean-Marc Bonard and Klaus Kern Ecole Polytechnique Federale de Lausanne, CH-05 Lausanne, Switzerland Max-Planck-Institut
More informationSEMICONDUCTOR PHYSICS REVIEW BONDS,
SEMICONDUCTOR PHYSICS REVIEW BONDS, BANDS, EFFECTIVE MASS, DRIFT, DIFFUSION, GENERATION, RECOMBINATION February 3, 2011 The University of Toledo, Department of Physics and Astronomy SSARE, PVIC Principles
More informationComputational Materials Design and Discovery Energy and Electronic Applications Synthesis Structure Properties
Computational Materials Design and Discovery Energy and Electronic Applications Synthesis Structure Properties Supercapacitors Rechargeable batteries Supercomputer Photocatalysts Fuel cell catalysts First
More informationFirst-Passage Kinetic Monte Carlo Algorithm for Complex Reaction-Diffusion Systems
First-Passage Kinetic Monte Carlo Algorithm for Complex Reaction-Diffusion Systems Aleksandar Donev 1 Lawrence Postdoctoral Fellow Lawrence Livermore National Laboratory In collaboration with: Vasily V.
More information6. Computational Design of Energy-related Materials
6. Computational Design of Energy-related Materials Contents 6.1 Atomistic Simulation Methods for Energy Materials 6.2 ab initio design of photovoltaic materials 6.3 Solid Ion Conductors for Fuel Cells
More informationToday s Outline - April 07, C. Segre (IIT) PHYS Spring 2015 April 07, / 30
Today s Outline - April 07, 2015 C. Segre (IIT) PHYS 570 - Spring 2015 April 07, 2015 1 / 30 Today s Outline - April 07, 2015 PHYS 570 days at 10-ID C. Segre (IIT) PHYS 570 - Spring 2015 April 07, 2015
More informationStudies on bi-directional hydrogen isotopes permeation through the first wall of a magnetic fusion power reactor
Studies on bi-directional hydrogen isotopes permeation through the first wall of a magnetic fusion power reactor IAEA-CRP Plasma-Wall Interaction with Reduced Activation Steel Surfaces in Fusion Devices
More informationOutlook: Application of Positron Annihilation for defects investigations in thin films. Introduction to Positron Annihilation Methods
Application of Positron Annihilation for defects investigations in thin films V. Bondarenko, R. Krause-Rehberg Martin-Luther-University Halle-Wittenberg, Halle, Germany Outlook: Introduction to Positron
More informationIn situ TEM studies of helium bubble/platelet evolution in Si based materials
In situ TEM studies of helium bubble/platelet evolution in Si based materials M. Vallet 1, M.F. Beaufort 1, J.F. Barbot 1, E. Oliviero 2 and S.E. Donnelly 3 1 Institut Pprime, CNRS-Université de Poitiers,
More informationOverview of scattering, diffraction & imaging in the TEM
Overview of scattering, diffraction & imaging in the TEM Eric A. Stach Purdue University Scattering Electrons, photons, neutrons Radiation Elastic Mean Free Path (Å)( Absorption Length (Å)( Minimum Probe
More informationModelling Austenitic Stainless Steels for Fusion Reactors. 18 December, 2003 Sonny Martin Tevis Jacobs Yucheng Zhang Jiawen Chen
Modelling Austenitic Stainless Steels for Fusion Reactors 18 December, 23 Sonny Martin Tevis Jacobs Yucheng Zhang Jiawen Chen 1 Abstract The irradiation hardening of austenitic stainless steel in fusion
More informationNon-empirical prediction of impurity segregation in α-fe from first principles. Abstract
APS/123-QED Non-empirical prediction of impurity segregation in α-fe from first principles T. Tsuru, 1, C. Suzuki, 1 Y. Kaji, 1 and T. Tsukada 1 1 Nuclear Science and Engineering Directorate, Japan Atomic
More informationStudying Metal to Insulator Transitions in Solids using Synchrotron Radiation-based Spectroscopies.
PY482 Lecture. February 28 th, 2013 Studying Metal to Insulator Transitions in Solids using Synchrotron Radiation-based Spectroscopies. Kevin E. Smith Department of Physics Department of Chemistry Division
More informationYield maps for nanoscale metallic multilayers
Scripta Materialia 50 (2004) 757 761 www.actamat-journals.com Yield maps for nanoscale metallic multilayers Adrienne V. Lamm *, Peter M. Anderson Department of Materials Science and Engineering, The Ohio
More informationModelling of the diffusion of self-interstitial atom clusters in Fe-Cr alloys
Modelling of the diffusion of self-interstitial atom clusters in Fe-Cr alloys Dmitry Terentyev, Lorenzo Malerba, Alexander V Barashev To cite this version: Dmitry Terentyev, Lorenzo Malerba, Alexander
More informationOpen Access. Suman Chakraborty* Q T + S gen = 1 S 1 S 2. Department of Mechanical Engineering, Indian Institute of Technology, Kharagpur , India
he Open hermodynamics Journal, 8,, 6-65 6 Open Access On the Role of External and Internal Irreversibilities towards Classical Entropy Generation Predictions in Equilibrium hermodynamics and their Relationship
More informationDensity Functional Modeling of Nanocrystalline Materials
Density Functional Modeling of Nanocrystalline Materials A new approach for modeling atomic scale properties in materials Peter Stefanovic Supervisor: Nikolas Provatas 70 / Part 1-7 February 007 Density
More informationNUCLEAR TRANSMUTATION IN DEUTERED PD FILMS IRRADIATED BY AN UV LASER
Castellano, et al. Nuclear Transmutation in Deutered Pd Films Irradiated by an UV Laser. in 8th International Conference on Cold Fusion. 2000. Lerici (La Spezia), Italy: Italian Physical Society, Bologna,
More informationN = N A Pb A Pb. = ln N Q v kt. = kt ln v N
5. Calculate the energy for vacancy formation in silver, given that the equilibrium number of vacancies at 800 C (1073 K) is 3.6 10 3 m 3. The atomic weight and density (at 800 C) for silver are, respectively,
More informationSUPPLEMENTARY INFORMATION
In the format provided by the authors and unedited. Intrinsically patterned two-dimensional materials for selective adsorption of molecules and nanoclusters X. Lin 1,, J. C. Lu 1,, Y. Shao 1,, Y. Y. Zhang
More informationAberration-corrected TEM studies on interface of multilayered-perovskite systems
Aberration-corrected TEM studies on interface of multilayered-perovskite systems By Lina Gunawan (0326114) Supervisor: Dr. Gianluigi Botton November 1, 2006 MSE 702(1) Presentation Outline Literature Review
More informationComparisons of DFT-MD, TB- MD and classical MD calculations of radiation damage and plasmawallinteractions
CMS Comparisons of DFT-MD, TB- MD and classical MD calculations of radiation damage and plasmawallinteractions Kai Nordlund Department of Physics and Helsinki Institute of Physics University of Helsinki,
More informationJoint ICTP-IAEA Workshop on Physics of Radiation Effect and its Simulation for Non-Metallic Condensed Matter.
2359-16 Joint ICTP-IAEA Workshop on Physics of Radiation Effect and its Simulation for Non-Metallic Condensed Matter 13-24 August 2012 Introduction to atomistic long time scale methods Roger Smith Loughborough
More informationModule 16. Diffusion in solids II. Lecture 16. Diffusion in solids II
Module 16 Diffusion in solids II Lecture 16 Diffusion in solids II 1 NPTEL Phase II : IIT Kharagpur : Prof. R. N. Ghosh, Dept of Metallurgical and Materials Engineering Keywords: Micro mechanisms of diffusion,
More informationSputtering Yield of Noble Gas Irradiation onto Tungsten Surface
J. Adv. Simulat. Sci. Eng. Vol. 3, No. 2, 165 172. c 2016 Japan Society for Simulation Technology Sputtering Yield of Noble Gas Irradiation onto Tungsten Surface Hiroaki Nakamura 1,2,*, Seiki Saito 3,
More informationThin Film Bi-based Perovskites for High Energy Density Capacitor Applications
..SKELETON.. Thin Film Bi-based Perovskites for High Energy Density Capacitor Applications Colin Shear Advisor: Dr. Brady Gibbons 2010 Table of Contents Chapter 1 Introduction... 1 1.1 Motivation and Objective...
More informationBasic Effects of Radiation. J. M. Perlado Director Instituto de Fusión Nuclear
Basic Effects of Radiation J. M. Perlado Director Instituto de Fusión Nuclear R&D in Advanced Materials Materials Science Investigating the relationship between structure and properties of materials. Materials
More informationInteraction of ion beams with matter
Interaction of ion beams with matter Introduction Nuclear and electronic energy loss Radiation damage process Displacements by nuclear stopping Defects by electronic energy loss Defect-free irradiation
More informationInfluence of the specificities of ion irradiation on the nanostructural evolution in Fe alloys: an object kinetic Monte Carlo study
Influence of the specificities of ion irradiation on the nanostructural evolution in Fe alloys: an object kinetic Monte Carlo study Monica Chiapetto 1,2, Lorenzo Malerba 1, Nicolas Castin 1, Cornelia Heintze
More informationA constant potential of 0.4 V was maintained between electrodes 5 and 6 (the electrode
(a) (b) Supplementary Figure 1 The effect of changing po 2 on the field-enhanced conductance A constant potential of 0.4 V was maintained between electrodes 5 and 6 (the electrode configuration is shown
More informationMesoporous titanium dioxide electrolyte bulk heterojunction
Mesoporous titanium dioxide electrolyte bulk heterojunction The term "bulk heterojunction" is used to describe a heterojunction composed of two different materials acting as electron- and a hole- transporters,
More informationMeasurement and modelling of hydrogen uptake and transport. Alan Turnbull
Measurement and modelling of hydrogen uptake and transport Alan Turnbull Hydrogen gas (+ H 2 O vapour, H 2 S) dissociation General and localised corrosion, cathodic protection, galvanic coupling; electroplating
More informationAdvanced Analytical Chemistry Lecture 12. Chem 4631
Advanced Analytical Chemistry Lecture 12 Chem 4631 What is a fuel cell? An electro-chemical energy conversion device A factory that takes fuel as input and produces electricity as output. O 2 (g) H 2 (g)
More informationUnique phenomena of tungsten associated with fusion reactor: uncertainties of stable hydrogen configuration tapped in tungsten vacancy
Unique phenomena of tungsten associated with fusion reactor: uncertainties of stable hydrogen configuration tapped in tungsten vacancy Kyushu University Kazuhito Ohsawa Technical Meeting of the International
More informationChapter 3 Modeling and Simulation of Dye-Sensitized Solar Cell
Chapter 3 Modeling and Simulation of Dye-Sensitized Solar Cell 3.1. Introduction In recent years, dye-sensitized solar cells (DSSCs) based on nanocrystalline mesoporous TiO 2 films have attracted much
More informationSputtering by Particle Bombardment I
Sputtering by Particle Bombardment I Physical Sputtering of Single-Element Solids Edited by R. Behrisch With Contributions by H. H. Andersen H.L. Bay R. Behrisch M. T. Robinson H.E. Roosendaal R Sigmund
More informationInvestigations of the effects of 7 TeV proton beams on LHC collimator materials and other materials to be used in the LHC
Russian Research Center Kurchatov Institute Investigations of the effects of 7 ev proton beams on LHC collimator materials and other materials to be used in the LHC A.I.Ryazanov Aims of Investigations:
More informationModeling of charge collection efficiency degradation in semiconductor devices induced by MeV ion beam irradiation
Modeling of charge collection efficiency degradation in semiconductor devices induced by MeV ion beam irradiation Ettore Vittone Physics Department University of Torino - Italy 1 IAEA Coordinate Research
More informationConduction Modeling in Mixed Alkali Borate Glasses
International Journal of Pure & Applied Physics ISSN 0973-1776 Vol.1 No.2 (2005), pp. 191-197 Research India Publications http://www.ripub lication.com/ijpap.htm Conduction Modeling in Mixed Alkali Borate
More informationUC Berkeley UC Berkeley Previously Published Works
UC Berkeley UC Berkeley Previously Published Works Title Accessing Defect Dynamics using Intense, Nanosecond Pulsed Ion Beams Permalink https://escholarship.org/uc/item/4jx927qh Authors Persaud, A Barnard,
More information1 One-Dimensional, Steady-State Conduction
1 One-Dimensional, Steady-State Conduction 1.1 Conduction Heat Transfer 1.1.1 Introduction Thermodynamics defines heat as a transfer of energy across the boundary of a system as a result of a temperature
More informationKinetics. Rate of change in response to thermodynamic forces
Kinetics Rate of change in response to thermodynamic forces Deviation from local equilibrium continuous change T heat flow temperature changes µ atom flow composition changes Deviation from global equilibrium
More informationAn Overview of Plutonium Aging
LA-UR-03-4111 An Overview of Plutonium Aging Joe Martz, David Clark, Luis Morales, Kathi Alexander Los Alamos National Laboratory Plutonium Futures Conference 2003 1 Plutonium Aging Studies Objectives
More informationNANOFLUIDS. Abstract INTRODUCTION
NANOFLUIDS Abstract Suspended nano particles in conventional fluids are called nanofluids...recent development of nanotechnology brings out a new heat transfer coolant called 'nanofluids'. These fluids
More informationImplantation Energy Dependence on Deuterium Retention Behaviors for the Carbon Implanted Tungsten
J. Plasma Fusion Res. SERIES, Vol. 10 (2013) Implantation Energy Dependence on Deuterium Retention Behaviors for the Carbon Implanted Tungsten Yasuhisa Oya 1) *, Makoto Kobayashi 1), Naoaki Yoshida 2),
More informationComparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices
Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices G.M. Wright 1, D. Brunner 1, M.J. Baldwin 2, K. Bystrov 3, R. Doerner 2, B. LaBombard 1, B. Lipschultz 1, G. de Temmerman 3,
More informationModelling of radiation damage in tungsten including He production
Modelling of radiation damage in tungsten including He production C.S. Becquart 1, C. Domain 2 A. De Backer 1 M.F. Barthe 3 M. Hou 4, C. Ortiz 5 1 Unité Matériaux Et Techniques, UMET, UMR 8207, Villeneuve
More informationTritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket
Tritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket I. Ricapito 1), P. Calderoni 1), A. Ibarra 2), C. Moreno 2), Y. Poitevin
More informationEE 212 FALL ION IMPLANTATION - Chapter 8 Basic Concepts
EE 212 FALL 1999-00 ION IMPLANTATION - Chapter 8 Basic Concepts Ion implantation is the dominant method of doping used today. In spite of creating enormous lattice damage it is favored because: Large range
More informationSwift heavy ion irradiation effects. in condensed matter. K. Havancsák
Swift heavy ion irradiation effects in condensed matter K. Havancsák HAS-JINR Workshop 2004 Hungarian Academy of Sciences Joint Institute for Nuclear Research Use of heavy ions High energy heavy ion beams
More informationEfficient Hydrogen Evolution. University of Central Florida, 4000 Central Florida Blvd. Orlando, Florida, 32816,
Electronic Supplementary Material (ESI) for Energy & Environmental Science. This journal is The Royal Society of Chemistry 2017 MoS 2 /TiO 2 Heterostructures as Nonmetal Plasmonic Photocatalysts for Highly
More informationNEUTRONIC ANALYSIS STUDIES OF THE SPALLATION TARGET WINDOW FOR A GAS COOLED ADS CONCEPT.
NEUTRONIC ANALYSIS STUDIES OF THE SPALLATION TARGET WINDOW FOR A GAS COOLED ADS CONCEPT. A. Abánades, A. Blanco, A. Burgos, S. Cuesta, P.T. León, J. M. Martínez-Val, M. Perlado Universidad Politecnica
More informationMolecular dynamics modelling of radiation damage in normal, partly inverse and inverse spinels
Loughborough University Institutional Repository Molecular dynamics modelling of radiation damage in normal, partly inverse and inverse spinels This item was submitted to Loughborough University's Institutional
More informationPhysics 156: Applications of Solid State Physics
Physics 156: Applications of Solid State Physics Instructor: Sue Carter Office NSII 349 Office Hours: Wednesdays 11:30 to 1 pm or by appointment Email: sacarter@ucsc.edu Book: http://ece-www.colorado.edu/~bart/book/book/title.htm
More informationSafety Assessment on the Storage of Irradiated Graphite Waste Produced from the Decommissioning of KRR-2
Safety Assessment on the Storage of Irradiated Graphite Waste Produced from the Decommissioning of KRR-2 D.G. Lee, G.H. Jeong, W.Z. Oh, K.W. Lee Korea Atomic Energy Research Institute Korea ABSTRACT Irradiated
More information